Droplet impaction on the wall surface is ubiquitous in natural and industrial applications.
Understanding this phenomenon is also significant to nuclear installation design and safety …

Accident tolerant fuel deployment has been rapidly accelerating in the US with lead test rods
and assemblies already inserted in commercial reactors. With the current deployment target …

When the water inventory evaporates during a hypothetical loss of coolant accident in the
core of a pressurized water reactor, the fuel rods temperature increases substantially …

Reflooding experiments with rod bundles at Loss Of Coolant Accident (LOCA) conditions
usually use intrusive methods with limited access and, consequently, their data are not …

Much effort has been devoted by the nuclear community to develop mechanistic models to
predict the heat dissipation of fuel rods during a loss of coolant accident (LOCA). However …

During a loss of coolant accident (LOCA), blocked sub-channels may appear due to the
swelling of the fuel rods' cladding, which results in flow redistribution during the reflooding …

The behavior of cladding melting and melt migration is an important phenomenon during the
early stage of core disruptive accidents (CDA) in lead-cooled fast reactors (LFRs), which can …

During reflood conditions following a loss-of-coolant accident in pressurized water reactors,
droplet flow affects the heat and mass transfer between liquid and steam phases. Flow …

Droplet-wall impaction exists in many nuclear installations and severe accidents. In this
study, we experimentally investigate a single droplet impinging on a heated and inclined …

During a severe power plant accident, steam condensation mitigates containment
pressurization in a postulated nuclear accident. Understanding the condensation process of …